Search Results - "Menard, J.E."
-
1
Stability and transport of gyrokinetic critical pedestals
Published in Nuclear fusion (01-08-2024)“…Abstract A gyrokinetic threshold model for pedestal width–height scaling prediction is applied to multiple devices. A shaping and aspect ratio scan is…”
Get full text
Journal Article -
2
Efficient ECCD non-inductive plasma current start-up, ramp-up, and sustainment for an ST fusion reactor
Published in Nuclear fusion (01-08-2024)“…Abstract The elimination of the need for an Ohmic heating solenoid may be the most impactful design driver for the realization of economical compact fusion…”
Get full text
Journal Article -
3
Extending the low-recycling, flat temperature profile regime in the lithium tokamak experiment-β (LTX-β) with ohmic and neutral beam heating
Published in Nuclear fusion (01-05-2023)“…Abstract Recent experiments in the lithium tokamak experiment- β (LTX- β ) have extended the duration, performance, operating conditions, and diagnosis of the…”
Get full text
Journal Article -
4
In search of X-point radiator regime features in NSTX and DIII-D discharges with the snowflake divertor
Published in Nuclear materials and energy (01-12-2024)“…Experimental data from NSTX and DIII-D discharges with the snowflake (SF) divertor configurations are analyzed toward the development of the X-point radiator…”
Get full text
Journal Article -
5
Advanced divertor configurations with large flux expansion
Published in Journal of nuclear materials (01-07-2013)“…Experimental studies of the novel snowflake divertor concept (D. Ryutov, Phys. Plasmas 14 (2007) 064502) performed in the NSTX and TCV tokamaks are reviewed in…”
Get full text
Journal Article -
6
Divertor heat flux reduction and detachment experiments in NSTX
Published in Journal of nuclear materials (15-06-2007)“…We report the first successful experiments at achieving significant outer divertor peak heat flux reduction, from 4–7MW/m2 to 1–2MW/m2, in 4MW NBI-heated…”
Get full text
Journal Article Conference Proceeding -
7
Architectural development of an ST fusion device
Published in Fusion engineering and design (01-07-2023)“…A recent U.S. National Academy study recommended the development of a next step Sustained High Power Density (SHPD) facility within the U.S. as an intermediate…”
Get full text
Journal Article -
8
NSTX-U research advancing the physics of spherical tokamaks
Published in Nuclear fusion (01-11-2024)“…Abstract The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low- A ,…”
Get full text
Journal Article -
9
The development of a Sustained High Power Density (SHPD) facility
Published in Fusion engineering and design (01-07-2021)“…A Sustained High Power Density (SHPD) facility is being planned within the U.S. as a non DT device which can be a bridge to a Compact Fusion Pilot Plant (CFPP)…”
Get full text
Journal Article -
10
Edge-localized-mode suppression through density-profile modification with lithium-wall coatings in the National Spherical Torus Experiment
Published in Physical review letters (14-08-2009)“…Reduction or elimination of edge localized modes (ELMs) while maintaining high confinement is essential for future fusion devices, e.g., the ITER. An ELM-free…”
Get full text
Journal Article -
11
Observation of plasma toroidal-momentum dissipation by neoclassical toroidal viscosity
Published in Physical review letters (09-06-2006)“…Dissipation of plasma toroidal angular momentum is observed in the National Spherical Torus Experiment due to applied nonaxisymmetric magnetic fields and their…”
Get full text
Journal Article -
12
Active control of divertor heat and particle fluxes in EAST towards advanced steady state operations
Published in Journal of nuclear materials (01-08-2015)“…Significant progress has been made in EAST towards advanced steady state operations by active control of divertor heat and particle fluxes. Many innovative…”
Get full text
Journal Article -
13
“Snowflake” divertor configuration in NSTX
Published in Journal of nuclear materials (01-08-2011)“…Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density…”
Get full text
Journal Article Conference Proceeding -
14
Accelerating the numerical simulation of magnetic field lines in tokamaks using the GPU
Published in Fusion engineering and design (01-06-2011)“…► Tokamak magnetic field lines are simulated on a GPU. ► Numerical integration of a set of nonlinear differential equations is required. ► Using the GPU yields…”
Get full text
Journal Article -
15
The enhanced pedestal H-mode in the National Spherical Torus experiment
Published in Journal of nuclear materials (15-06-2009)“…Typical H-mode pedestal electron and ion temperatures in NSTX range from 100–300 eV. A new operating regime termed the ‘enhanced pedestal’ (EP) H-mode has been…”
Get full text
Journal Article Conference Proceeding -
16
Structure of MARFEs and ELMs in NSTX
Published in Journal of nuclear materials (15-06-2007)“…The fast-evolving structure of MARFEs and ELMs is observed in the National Spherical Torus Experiment (NSTX) using a fast-framing camera. It is shown that Type…”
Get full text
Journal Article Conference Proceeding -
17
Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution
Published in 2015 IEEE 26th Symposium on Fusion Engineering (SOFE) (01-05-2015)“…Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large…”
Get full text
Conference Proceeding -
18
ELMs and the H-mode pedestal in NSTX
Published in Journal of nuclear materials (01-03-2005)“…We report on the behavior of ELMs in NBI-heated H-mode plasmas in NSTX. It is observed that the size of Type I ELMs, characterized by the change in plasma…”
Get full text
Journal Article -
19
Status of the control system on the National Spherical Torus Experiment (NSTX)
Published in Fusion engineering and design (01-07-2006)“…In 2003, the National Spherical Torus Experiment (NSTX) plasma control system was used for plasma shape control using real-time equilibrium reconstruction…”
Get full text
Journal Article -
20
Storage and analysis techniques for fast 2D camera data on NSTX
Published in Fusion engineering and design (01-07-2006)“…Animations from fast 2D camera data are facilitating the investigation of spatially distributed phenomena in high-temperature plasmas. The National Spherical…”
Get full text
Journal Article Conference Proceeding